Methods for steady state thermal-hydraulic analysis of pressurized water reactor cores
Name
MIT-EL-76-006-22332153.pdf
Size
12.67 MB
Format
Adobe PDF
Checksum (MD5)
312c35f98a2634fc29fd31f66280cea6
Author(s)
Moreno Palacios, Pablo
Chiu, Chong
Date Issued
1976
Publisher
MIT Energy Lab
Series/Report no.
MIT-EL
76-006
Abstract
A one-pass simplified analysis method for steady state PWR
core has been developed. The advantages over the other multistage
approaches have been discussed and compared- Recommended nodal
patterns for modelling the reactor core have been proposed. Also
the effect due to the lumped channel technique utilized in both
the simplified method and existing multistage methods has been investigated for both D and 3D problems. For the nodal pattern recommended
with the proposed one-pass analysis method, use of the lumped channel
technique introduces negligible errors.
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